EP0172355B1

EP0172355B1 - Fluid moderator control system reactor internals distribution system

Info

Publication number: EP0172355B1
Application number: EP85107668A
Authority: EP
Inventors: Howard Frank Fensterer; Luciano Veronesi; William Edward Klassen; David Edward Boyle; Robert Byron Salton
Original assignee: Westinghouse Electric Corp
Current assignee: CBS Corp
Priority date: 1984-07-02
Filing date: 1985-06-21
Publication date: 1989-04-12
Also published as: ES544696A0; KR860001431A; JPS6120890A; US4661306A; ES8800778A1; EP0172355A1

Description

This invention relates in general to spectral shift, pressurized light water nuclear reactors and in particular to a reactor internals system for distributing the flow of a low neutron fluid moderator to the core of the reactor to achieve the spectral shift.
In conventional, state of the art, pressurized light water nuclear reactors, the reactor core is designed to contain excess reactivity. As the reactor operates, the excess reactivity is very gradually consumed until such point as the reactor core will no longer sustain the nuclear reaction and then the reactor must be refuelled. Usually this occurs over a period of years. It is very advantageous to maximize the time between reactor refuellings (extend the life of the core) since refuelling requires complete shutdown of the reactor and is quite time consuming. Extending the life of the core is usually accomplished by providing the core with a significant amount of excess reactivity.
Typically, control over the fission process, or reactivity control, including control necessitated by the excess reactivity is accomplished by varying the amount of neutron-absorbing materials within the core of the reactor. Control rods which contain neutron-absorbing materials and are movable into and out of the core provide one method of controlling the reactivity. Burnable and nonburnable poisons dissolved in the reactor coolant provide another method of reactivity control. As the reactivity decreases, due to reactor operation, the poisons are gradually removed by being burned by reactor operation or are physically removed by a separate system designed for such purpose. Most often, a combination of dissolved poisons and control rods are used to control the reactor and the excess reactivity.
Unfortunately, control with control rods and poisons, absorb neutrons which could otherwise be used in a productive manner. For example, the neutrons produced by the excess reactivity could be used to convert fertile materials within the fuel assemblies to plutonium or fissile uranium which can then be fissioned and contribute to an even further extension of core life. Thus, while the use of control rods and dissolved poisons provide very effective reactor control, their use comprises a relatively inefficient depletion of high cost uranium. It would be, therefore, advantageous to control the excess reactivity but not suppress the neutrons associated with the excess reactivity, in order to further extend core life or time between refuellings, and to lower fuel costs.
It is known that fuel element enrichment can be reduced and the conversion ratio of producing fissile materials can be increased by employing a "hardened" (nuclear energy) spectrum during the first part of the fuel cycle to reduce excessive reactivity and to increase the conversion of fertile material to fissile material; then employing a "softer" (lower energy) neutron spectrum during the latter part of the fuel cycle to increase reactivity and extend the core life by fissioning the previously generated fissile material. One such method utilizing the above is known as spectral shift control which provides a reactor with an extended core life while reducing the amount of neutron-absorbing material in the reactor core. One example of such method of control comprises a mechanical spectral shift reactor whereby hollow displacer rods are provided within fuel assemblies within the core (which, of course, displace an equal volume of water within the fuel assemblies) and which are mechanically withdrawn or punctured as in FR-A-2 498 800, to accomplish water flooding of the available volume. In the early stages of core life, the neutron spectrum is hardened by the displacement of a portion of the water within the core by the displacer rods. The spectrum is later softened by the addition of water within the core by the aforesaid rod withdrawal or puncturing.
Another method of achieving a spectral shift is to utilize heavy water or deuterium oxide to replace an equivalent volume of core water during the early stages of core life then to gradually reduce the volume of heavy water and replace it with regular reactor coolant (light water) during the later stages of core life. The less effective moderator, heavy water, allows for less fuel enrichment and a higher ratio of converting fertile material to fissile material which in combination provides for a reduction of fuel costs and an extension of core life. An example of this art is found in Patent Application EP-A-85 107666.1 entitled "Fuel Assembly", and assigned to Wes- tinghouse Electric Corporation.
In the "Fuel Assembly" patent application, there is explained the need to introduce heavy water into the core support plate for distribution to the fuel assemblies and for eventually exiting the heavy water from the fuel assemblies and through and out of the core support plate.
However, while such requirements of a spectral shift nuclear reactor are well known, to data no apparatus exists which effectively and practically accomplishes such requirements. Also, there is a corresponding need to introduce and exit the deuterium oxide into and out of the pressure vessel. Again, no apparatus to accomplish the same is presently known to exist.
It is, therefore, the primary object of the present invention to provide a distribution system for introducing into the reactor pressure vessel and into the core a moderator which is a less effective moderator than the normal reactor coolant in the early stages of core life and which permits the gradual replacement of the low neutron moderating fluid with the normal reactor coolant during the later stages of core life.
With this object in view, the present invention resides in a spectral shift pressurized water nuclear reactor employing a low neutron moderating fluid for the spectral shift, including a reactor pressure vessel, a core comprising a plurality of fuel assemblies, a core support plate, and tubes penetrating the reactor vessel for introducing said moderating fluid into said reactor vessel, characterized in that means are associated with the core support plate for distributing said moderating fluid to said fuel assemblies and a flow port structure is interposed between said penetration means and said distribution means for flow connecting said penetration means with said distribution means.
The core support plate is provided with a plurality of flow zones with each zone receiving and distributing the low neutron moderator to the inlet of the fuel assemblies within each zone and from the outlet of the same fuel assemblies. Separate inlet and outlet ports are used for each zone.
The invention will become more readily apparent from the following description of a preferred embodiment thereof shown, by way of example only, in the accompanying drawings, in which:

Figure 1 illustrates one embodiment of the present invention depicting in cross section a lower portion of the reactor pressure vessel and internals including the pressure vessel penetration, port, core support plate and fuel assembly inlet nozzle;
Figure 2 is a plan view of the core support plate showing the details of the flow distribution system;
Figure 3 is a sectional view of the core support plate of Figure 2 taken along the line III-III;
Figure 4 is a side view of the core support plate of Figure 3;
Figure 5 is a schematic view of the core support plate of Figure 2 taken along the line V-V; and

Figure 6 shows another embodiment of the present invention, particularly illustrating introduction of the low neutron moderating fluid from the upper portion of the reactor pressure vessel. Referring now to Figure 1 of the drawings there is shown a bottom portion of the pressure vessel 10, a penetration 11 through the wall of the pressure vessel 10, a lower core support plate 12, a port 13 connected between penetration 11 and the core support plate 12, and a lower flow inlet nozzle 14 having a seal connector 15 flow connected to the core support plate 12. A portion of a fuel assembly 16 is also shown, a plurality of which comprises the core of the reactor.
Penetration 11 includes a tubular or pipe member 20 which passes through the wall of the pressure vessel 10. A weld 21, around the circumference of tube 20, sealingly connects tube 20 to pressure vessel 10. Such penetration of the pressure vessel 10 is well known in the art. A venturi orifice 22 is provided within tube 20 for purposes which will be more fully explained hereinafter. A bolted flange 23 is sealed and structurally welded to tube 20. Penetration 11 comprises one of a plurality of inlet penetrations or outlet penetrations to pressure vessel 10. A low neutron moderator fluid such as deuterium oxide is caused to flow within penetration 11 so as to displace a portion of the core coolant within the fuel assemblies 16 with a predetermined amount of deuterium oxide which amount is consistent with the need at that given time to harden the nuclear spectrum and effectuate the spectral shift.
Port structure 13 flow connects penetration 11 with the flow channels in the core support plate 12. Port structure 13 comprises a lower substantially cylindrical member 24, an upper member 25, a bellows 26 connecting upper member 25 to lower member 24, and a skirt 27 surrounding bellows 26. As shown and described, port 13 is structurally connected at one end to flange 23 and at the other end to core support plate 12. Bellows 26 permits relative motion between upper member 25 and lower member 24 while maintaining a seal therebetween.
Lower member 24 of port structure 13 includes a flange 28 which sealingly mates with flange 23 on penetration 11. A metal "0" ring seal 29 may be used to effectuate the seal between flanges 23 and 28. Bolts 30 structurally secure flange members 23 and 28. A flow channel 31 within lower member 24 is axially aligned with the flow channel 32 in penetration 11 and with the flow channel 33 in upper member 25. Flow channels 31, 32 and 33 provide flow communication for the deuterium oxide introduced and controlled by said fluid moderator control system to the core support plate 12.
Upper member 25 of port structure 13 includes a lower cylindrical portion 34 which telescopically mates with the free upper end of member 24. One or more ring seals 35 which fit within circumferential grooves 36 in the free end 37 of member 24 provide a sliding seal between members 24 and 25. One end of bellows 26 is seal welded to the lower end 34 of member 25 while the other end of bellows 26 is seal welded to a cylindrical portion of member 24 in the vicinity of flange 28. In this manner, bellows 26 is given a length which provides for the differential thermal expansion between upper 25 and lower 24 members while minimizing any spring force exerted by bellows 26 resulting from such differential expansion. Skirt 27 may be secured at one end thereof to either upper member 25 or lower member 24. As shown, skirt 27 is welded to member 25. A tab 38 on the unsecured end of skirt 27 fits within a slot 39 in member 24 so as to limit the unrestrained motion between members 24 and 25 prior to assembly to the reactor and to prevent damage to telescoping portions of members 24 and 25. The control portion 40 of skirt 27 is slightly enlarged so as to fit closely within an opening 41 in guide plate 42 and to limit any lateral deflection of port 13 during reactor operation. A greater amount of clearance is provided between opening 41 and the main portions of skirt 27 to facilitate assembly of guide plate 42 over the plurality of ports 13 co- extending from the bottom of the reactor vessel 10.
The upper end of member 25 provides for attachment of port 13 to the lower core support plate 12 and for ducting the flow of the low neutron moderating fluid from within flow channel 33 (which is in flow communication with port structure 13) to one or more horizontal flow channels within core support plate 12. As previously described, the lower end of member 25 comprises a cylindrical hollow tube 34 (with flow channel 33 comprising the hollow center of said cylindrical tube) which telescopically mates with a plunger upper end 37 of lower member 24 of port 13. Flow channel 33 terminates within the lower end 34 of member 25 at a position slightly below the lower surface of the core support plate 12. Slightly above the terminal end of flow channel 33, the cylindrical portion 36 of member 25 necks down to form shank 43 having a solid circular cross-sectional shape. The shank extends upwards toward the end 44 of member 25 where the cross-sectional diameter is enlarged and is axially drilled and internally tapped 45. A shoulder 46 is formed between the shank 43 and the upper end of member 25. Shoulder 46 fits against the lower surface of the core support plate 12. Shank 43 and enlarged end 44 fit within an opening 47 in core support plate 12. A bolt 48 fitted through an opening 49 in the upper side of core support plate 12 threadingly engages with the enlarged upper end 44. Tightening bolt 47 causes shoulder 46 to firmly seat against the lower surface of the core support plate 12 and to effectuate a leak-free joint due to "0" ring seal 50 in groove 51 in shoulder 46. The opening 49 for bolt 48 is sealed by the use of another metallic "0" ring 52 provided within a groove 53 of cylindrical block 54 which is bolted 55 within the upper end of core support plate 12. In the manner provided, ports 13 may be assembled to the flanges 23 of penetrations 11 at the bottom of the pressure vessel 10 and then the reactor internals including the core support plate 12 may be lowered into position over the upper ends 44 of member 25. A tapered surface 56 also provided at end 44 facilitates such installation. Tightening of bolt 48 and installation of block 54 completes the assembly procedure.
The flow of the low moderating fluid from within flow channel 33 to the core support plate 12 is, as mentioned above, provided for by the upper end of member 25. One or more holes 57 are drilled at an angle (relative to the axial center line of member 25) from the intersection of shank 43 and cylindrical tube 36 into the opening comprising flow channel 33. Holes 57 provide flow communication between channel 33 and the distribution or the core support plate inlet flow channel 58 formed by hole 47 in core support plate 12 and the necked-down portion or shank 43 of member 25. It being noted that "0" ring seals 50 and 52 effectively seal off distribution channel 58 except for the horizontal openings in lower core support plate 12.
Figure 2 shows a detail one method of distributing the flow of the low neutron moderating fluid within the lower core support plate 12 (from flow channels 58 to the seal connectors 15 of the fuel assemblies) and for returning the flow of said fluid from the seal connectors 15 back through the lower core support to flow channels 58. In this regard, it is to be noted that seal connectors 15 may act as flow inlet or flow outlet connectors depending upon their location with respect to flow nozzle 14. Further explanation of this aspect may be found in the above-referenced copending patent application EP-85 107666.1.
The core support plate is divided into four separate regions 61A, 61B, 61C and 61D. Each region is simultaneously supplied with the low neutron moderating fluid introduced through a corresponding flow channel 58 in the core support plate 12. Such an arrangement facilitates uniform flow to each fuel assembly and precludes large reactivity additions in the unlikely event of an inadvertent displacement of the low neutron moderating fluid with a high neutron moderator such as the light water reactor coolant.
In order to provide the fuel assemblies within each region, 61A, 61B, 61C, 61D, with the low neutron moderator, a horizontal network of inlet and outlet flow channels is provided for each region 61A, 61B, 61C and 61D.
For simplicity, the flow arrangement for region 61B only will be described. It will be noted, however, that the same arrangement is applicable to the other regions 61A, 61C and 61D, although not explained in detail. Still referring to Figures 1 through 4, region 61B may be classified as a center region. A single flow inlet channel 58 intersects a single main feed line 62B which is horizontally drilled at level 63-3. Branch feed lines 64B are also drilled horizontally at the same level as line 62B at right angles to each other. In region 61 B there are four branch feed lines 64B.
A single main exit flow line 65B (intersecting with another channel 58) also services region 61 B. Similarly, four branch exit flow lines 66B services region 61B, which flow lines intersect with line 65B and are all at the same level 63-4 with each other. The main exit line 65B is at right angles to the four branch exit lines 66B.
As can be seen in Figures 3 and 4, levels 63-3 and 63-4 are different. Thus, none of the main or branch inlet lines interfere with the main or branch exit lines. A vertical flow line 68B is provided at the intersection of each inlet seal connector and the branch feed lines 64B while lines 69B are provided at the intersection of each outlet seal connector and the exit branch lines 66B. The arrangement thus provides a complete flow path within region 61B from channel 58 to each inlet flow seal connector and from each exit flow seal connector back to a different flow channel 58. The inlet and outlet flow paths in regions 61A, 61C and 61D are similar to that described for region 61 B.
Although there are two levels of flow lines (inlet and exit) for each region 61 A-61 D, the arrangement shown in Figures 1 through 4 requires a total of only four different levels. By way of clarification, flow level 63-1 services lines 62A, 62D, 64A and 64D; level 63-2 services lines 65A, 65D, 66A and 66D; level 63-3 services lines 62B, 62C, 64B and 64C; and, level 63-4 services lines 65B, 65C, 66B and 66C. In other words; each level services two functions for each of two flow regions. There are, of course, distinct advantages in minizing the total number of flow line levels. It simplifies machining; it minimizes the possibility of interference with the main coolant flow channels through the lower core support plate 12. Other advantages will be apparent to one skilled in the art.
All of the above-described horizontal flow lines may be gun drilled in the lower core support with the entrance or exit to the drilled hole sealed by a plug 70 fitted within the hole and seal welded 71 around its periphery as shown in Figure 5. In the alternative, a method of horizontal flow distribution can be accomplished by attaching a piping manifold to either or both of the upper and lower surfaces of the lower core support plate 12.
Figure 6 depicts an alternate method to supply the low neutron moderating fluid to the lower core support plate distribution system shown in Figures 2 through 5. In this embodiment, the fluid is introduced into the reactor vessel 10 through top entry (as opposed to the bottom entry of Figure 1). One or more penetrations 80 are welded to the pressure vessel in normal fashion. A flange 81 is welded to the internal diameter of the pressure vessel 10 at the location of penetration 80. A bellows 82, an elbow 83 and a bolted flange half 84 are connected to welded flange 81. The other half 85 of bolted flange is welded to a connecting pipe 86 which is in turn welded at 87 to the upper flange of the lower core barrel 88. Bellows 82 provides for differential thermal expansion between the reactor internals and the pressure vessel 10. Bolted flange halves 84 and 85 and connecting pipe 86 fit within an opening 89 in the flange 90 of the upper core support plate 91. The bolted flange 84 and 85 is provided to permit removal of elbow 83 if the lower internals are to be removed from the pressure vessel 10. A flow channel 92 is provided in flange 93 of the lower core barrel 88. A pipe 94 welded thereto and connected at its lower end to the horizontal flow inlet channels in the lower core support plate 12, completes the flow distribution system. The flow channel shown in Figure 6 may be used for fluid moderator inlet or outlet flow.
Venturi 22 comprises an insert within penetration 20 to permit flow of the low neutron moderating fluid to the core of the reactor but restrict outward flow of the moderating fluid in the very unlikely event of a double failure of penetration 20 outside the pressure vessel 10 and one or more of the seal connectors 15. Venturi 22 is of a type which is well known in the art.
The apparatus disclosed above has been described with regard to introducing a fluid such as deuterium oxide into the reactor core in order to effectuate spectral shift. The inventive apparatus is, of course, not intended to be limited to the flow of deuterium oxide. The flow of a suitable low moderating fluid may be used with the inventive apparatus. Additionally, the inventive apparatus contemplates the flow of a mixture of the low neutron moderating fluid in combination with the normal reactor coolant depending upon the degree of moderation required or desired at any time in accordance with the amount of excess reactivity then present in the core.
The inventive apparatus even further contemplates the ultimate displacement of the low neutron moderating fluid with the normal reactor coolant during the later stages of core life when a maximum amount of moderation is required especially when a soft nuclear spectrum is desired.
While the invention has been described, disclosed, illustrated and shown in certain terms or certain embodiments or modifications which it has assumed in practice, the scope of the invention is not intended to be nor should it be deemed to be limited thereby and such other modifications or embodiments as may be suggested by the teachings herein are particularly reserved especially as they fall within the breadth and scope of the claims here appended.

Claims

1. A spectral shift pressurized water nuclear reactor employing a low neutron moderating fluid for the spectral shift, including a reactor pressure vessel (10), a core comprising a plurality of fuel assemblies (16), a core support plate (12), and means (11) penetrating the reactor vessel (10) for introducing said moderating fluid into said reactor vessel (10), characterized in that means (58, 62B, 64B, 65B, 66B) are associated with the core support plate (12) for distributing said moderating fluid to said fuel assemblies (16) and a flow port structure (13) is interposed between said penetration means (11) and said distribution means (58, 62B, 64B, 65B, 66B) for flow connecting said penetration means (11) with said distribution means (58, 62B, 64B, 65B, 66B).

2. A reactor according to claim 1, characterized in that said means (11) for penetrating the reactor vessel comprises a pipe (20) passing through the wall of said reactor vessel (10), said pipe (20) being seal welded to said reactor vessel (10), the end of said pipe (20) within said reactor vessel having a flange (23) thereon.

3. A reactor according to claim 1 or 2, characterized in that said distribution means (58, 62B, 64B, 65B, 66B) associated with the core support plate (12) comprises at least one inlet flow channel (58), a plurality of branch inlet flow channels (64B) flow connected to said inlet flow channel (58) and a plurality of outlet flow channels (66B) flow connected to said branch inlet flow channels (64B) each outlet flow channel also being connected to a fuel assembly (16), a plurality of return flow channels (68B) each of which is connected to one of said fuel assemblies (16), a plurality of branch return flow channels (66B) flow connected to said fuel assembly return flow channels (68B) and at least one return flow outlet channel (62A) flow connected to said branch return flow channels (66B).

4. A reactor according to claim 3, characterized in that at least two separate flow regions are associated with said core support plate with each region including an inlet flow channel, a branch inlet flow channel, an outlet flow channel, a return flow channel (68B), a branch return flow channel (66B) and a return flow outlet channel (62A).

5. A reactor according to claims 1 to 4, characterized in that said flow port structure (13) comprises an elongated hollow member (24) fixedly connected at one end to said penetration means (11), and fixedly connected at the second end thereof to the core support plate (12), said flow port structure (13) having means (26) between said ends for sealingly varying the length of said flow port between said ends.

6. A reactor according to claims 1 to 5, characterized in that said flow port structure (13) comprises a first member (25) attached to said core support plate (12), a second member (24) attached to said penetration means (11) and said sealing means comprises a bellows (26) fixedly connected at one end to said first member (25) and fixedly connected at its other end to said second member (26).

7. A reactor according to claim 6, characterized in that the unconnected ends of said first and second members (25, 24) are telescopically arranged with a slideable seal (35) therebetween.

8. A reactor according to claim 7, characterized in that the unconnected end of said first member (25) comprises an elongated hollow tube portion (34) and the connected end comprises an elongated solid shank (43) with at least one flow channel (57) emanating from said hollow portion (34) and exiting at said shank (43).

9. A reactor according to claim 8, characterized in that said shank (43) of said flow port structure (13) fits within an opening (47) in said core support plate (12) with a space (58) between said opening (47) and said shank (43) said space (58) defining a flow channel connecting said flow port structure (13) to said core support plate distribution means (58, 62B, 64B, 65B, 66B).